Zobrazeno 1 - 7
of 7
pro vyhledávání: '"L. E. Conway"'
Publikováno v:
Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy. 207:259-268
In support of the development of AP600, Westinghouse is conducting two integral systems tests to examine the performance of the passive safety systems. A full-height, full-pressure test is being performed to simulate a small loss-of-coolant, steam ge
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::439c567b2d710a6e765fc933d804df36
https://doi.org/10.1243/pime_proc_1993_207_048_02
https://doi.org/10.1243/pime_proc_1993_207_048_02
Autor:
Carlo Lombardi, Bojan Petrovic, Francesco Oriolo, L. Cinotti, R.D. Boroughs, Davor Grgić, M. M. Moraes, L. Oriani, N. E. Todreas, J.M. Collado, D. T. Ingersoll, Hisashi Ninokata, Mario D. Carelli, Marco Enrico Ricotti, L. E. Conway, Antonio Carlos de Oliveira Barroso
Salient features of the International Reactor Innovative and Secure (IRIS) are presented here. IRIS, an integral, modular, medium size (335 MWe) PWR, has been under development since the turn of the century by an international consortium led by Westi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::de4f957d734c37d74eb9fe1d67a23c0c
https://www.bib.irb.hr/174925
https://www.bib.irb.hr/174925
Publikováno v:
10th International Conference on Nuclear Engineering, Volume 2.
IRIS (International Reactor Innovative and Secure) is a light water cooled, 335 MWe power reactor which is being designed by an international consortium as part of the US DOE NERI Program. IRIS features an integral reactor vessel that contains all th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cba0ff59495517a55a1c8b56f2f2337c
https://doi.org/10.1115/icone10-22572
https://doi.org/10.1115/icone10-22572
Publikováno v:
10th International Conference on Nuclear Engineering, Volume 2.
IRIS (International Reactor Innovative and Secure) is a light water cooled, 335 MWe power reactor which is being designed by an international consortium as part of the US DOE NERI Program. IRIS features an integral reactor vessel that contains all th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::20cd06b608d3f5837e9b0b64c9d12dc5
https://doi.org/10.1115/icone10-22571
https://doi.org/10.1115/icone10-22571
Autor:
Antonio Cammi, Francesco Oriolo, Chiara Lombardi, A. Cipollaro, Antonio Carlos de Oliveira Barroso, L. E. Conway, Andrea Cioncolini, Marco Enrico Ricotti
A deterministic analysis of the IRIS safety features has been carried out by means of the best-estimate code RELAP (ver. RELAP5 mod3.2). First, the main system components were modeled and tested separately, namely: the Reactor Pressure Vessel (RPV),
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bf098b5043ac6d7fad1db8a705ad8584
http://hdl.handle.net/11311/542149
http://hdl.handle.net/11311/542149
Autor:
Maurizio Bruzzone, Carlo Lombardi, L. Cinotti, G. Corsini, N. Meda, L. E. Conway, Marco Enrico Ricotti
Publikováno v:
10th International Conference on Nuclear Engineering, Volume 2.
IRIS (International Reactor Innovative and Secure) is a light water cooled, 335 MWe power reactor which is being designed by an international consortium as part of the US DOE NERI Program. IRIS features an integral reactor vessel that contains all th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7ce2fb3658ace762317f5ad91195dd8f
https://doi.org/10.1115/icone10-22570
https://doi.org/10.1115/icone10-22570